Development of Thermal/Irradiation Stress Analytical Code “VIENUS” for HTTR Graphite Block
Author:
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
http://www.tandfonline.com/doi/pdf/10.1080/18811248.1991.9731451
Reference16 articles.
1. Design of High Temperature Engineering Test Reactor (HTTR) and Associated Research and Development
2. Radiation creep of graphite. An introduction
3. Irradiation creep properties and strength of a fine-grained isotropic graphite
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